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Issue date | Title | Topic | |
---|---|---|---|
ML20195C627 | 28 May 1999 | Non-proprietary Rev 0 to Addendum to Topical Rept BAW-2346P, CR-3 Plant Specific MSLB Leak Rates | |
ML20196L203 | 19 May 1999 | Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs | Loop seal Non-Destructive Examination Weld Overlay Hydrostatic Probabilistic Risk Assessment Finite Element Analysis Large early release frequency Stress corrosion cracking Power change Flow Induced Vibration Exclusive Use Operational leakage |
ML20204D966 | 31 March 1999 | Non-proprietary Rev 1,Addendum a to BAW-2342, OTSG Repair Roll Qualification Rept | |
ML20248F744 | 31 May 1998 | Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity | |
ML17353A434 | 31 October 1995 | Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. | |
ML17264A118 | 31 July 1995 | Response to Part (1) of GL 92-01,Rev 1,Suppl 1. | |
ML20081B007 | 28 February 1995 | Nonproprietary Version of Crystal River Unit 3 Spent Fuel Storage Pool B Criticality Analysis | |
ML20101H416 | 31 May 1992 | Suppl 2 to Pressurizer Surge Line Thermal Stratification for B&W 177-FA Nuclear Plants,Summary Rept Fatigue Stress Analysis of Surge Line Elbows | Operating Basis Earthquake |
ML20067A524 | 31 December 1990 | Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' | Operating Basis Earthquake Finite Element Analysis Code Reconciliation Commercial Grade Power change |
ML20006A823 | 10 January 1990 | Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 | |
ML20135A557 | 31 August 1985 | B&W Owners Group Cavity Dosimetry Program | |
ML20138P154 | 2 July 1985 | Rev 1 to TMI-1 Nuclear Generating Station Natural Circulation Cooldown Analysis W/O Reactor Vessel Upper Head Void Formation, Topical Rept | |
ML20072M002 | 25 March 1983 | Abnormal Transient Operating Guidelines. Nine Oversize Drawings Encl.Aperture Cards Are Available in PDR | Boric Acid Shutdown Margin Emergency Lighting Fuel cladding Overspeed trip Subsequent actuation |
ML20107B271 | 30 June 1982 | Rev 1 to Analyses of Capsule B,Crystal River,Unit 3,Reactor Vessel Matls Surveillance Program | |
ML19296D385 | 1 February 1980 | Structural Effects of ATWS Overpressure Transients in Byron Jackson Primary Pumps. | |
ML19257A143 | 31 October 1979 | Auxiliary Feedwater Sys Reliability Analysis for Facility | Earthquake |
ML19319C817 | 15 July 1977 | Reactor Bldg Spray & ECCS Storage Tanks Drawdown Transient Analysis. Prepared for Util | Boric Acid |
ML19308D722 | 30 June 1976 | App I Analysis,Crystal River, Revision 2,June 1976. Prepared for Util.Includes Part of Table 6 Re Release Rates & Release Heights of Gaseous Element Only | |
ML20116J952 | 20 May 1970 | Dynamic Analysis of Vital Piping Sys Subjected to Seismic Motion | Safe Shutdown Operability Determination Earthquake |